• DocumentCode
    3124413
  • Title

    Natural convection cooling for LEU irradiated fuel plates

  • Author

    El Maaty, Talal Abou

  • fYear
    2010
  • fDate
    19-22 Dec. 2010
  • Firstpage
    413
  • Lastpage
    418
  • Abstract
    Different thermal hydraulic limiting phenomena´s are important to be studied during the natural convection cooling of a hypothetical irradiated Low Enriched Uranium (LEU) plate´s target. The irradiated LEU targets are used for the production of the medical isotope molybdenum -99 (Mo-99), whose decay product, technetium -99 (Tc-99) is used in the majority of medical diagnostic imaging procedures. After the irradiation of LEU targets, they are acquired a high level of radioactivity, so the direct handling and maneuvering for them is quite difficult. The targets should stay a period of time for cooling either at the reactor core or at the storage basket inside the reactor main pool. So, this study was performed to insure the thermal-hydraulic limiting phenomena´s (Onset of Nucleate Boiling, Pulsed Boiling Power ration, Onset of Net Vapor Generation and Burn - out Power ratio) during the natural convection cooling mode with variant power ratio (plate decay power at the time of establishment of natural convection regime to the steady state plate full power). The study was performed at two different positions, the first position was inside the reactor core where a long chimney exist while the other was in the storage basket. The study was aimed to evaluate the optimum power ratio, that is a function of time, at which the targets could transfer from the reactor core into the storage basket. The LEU targets had two possibilities during the irradiation, half load and full load irradiations. Both of the possibilities were discussed and analyzed at different power ratios. All the limiting phenomena´s were satisfied the thermal-hydraulic safety margins except the Onset of Nucleate Boiling Ratio, it had some considerations.
  • Keywords
    fission reactor cooling; fission reactor core control; fission reactor fuel; fission reactor safety; LEU irradiated fuel plates; LEU plate target; Low Enriched Uranium; medical diagnostic imaging procedures; medical isotope molybdenum; natural convection cooling; nucleate boiling ratio; radioactivity level; reactor core; reactor main pool; storage basket; thermal hydraulic limiting phenomena; thermal-hydraulic safety margins; Coolants; Fuels; Heat transfer; Heating; Inductors; Safety;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Thermal Issues in Emerging Technologies Theory and Applications (ThETA), 2010 3rd International Conference on
  • Conference_Location
    Cairo
  • Print_ISBN
    978-1-61284-268-4
  • Type

    conf

  • DOI
    10.1109/THETA.2010.5766424
  • Filename
    5766424